CN217448726U - Neutron capture therapy system - Google Patents

Neutron capture therapy system Download PDF

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Publication number
CN217448726U
CN217448726U CN202220138407.0U CN202220138407U CN217448726U CN 217448726 U CN217448726 U CN 217448726U CN 202220138407 U CN202220138407 U CN 202220138407U CN 217448726 U CN217448726 U CN 217448726U
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neutron
therapy system
capture therapy
chamber
neutron capture
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刘渊豪
卢威骅
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China Boron Xiamen Medical Equipment Co ltd
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China Boron Xiamen Medical Equipment Co ltd
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    • A—HUMAN NECESSITIES
    • A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00—Radiation therapy
    • A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N5/1077—Beam delivery systems
    • A61N5/1083—Robot arm beam systems
    • A—HUMAN NECESSITIES
    • A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00—Radiation therapy
    • A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A—HUMAN NECESSITIES
    • A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00—Radiation therapy
    • A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N5/1077—Beam delivery systems
    • A—HUMAN NECESSITIES
    • A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00—Radiation therapy
    • A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N5/1077—Beam delivery systems
    • A61N5/1079—Sharing a beam by multiple treatment stations
    • H—ELECTRICITY
    • H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05H—PLASMA TECHNIQUE; PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS
    • H05H3/00—Production or acceleration of neutral particle beams, e.g. molecular or atomic beams
    • H05H3/06—Generating neutron beams
    • A—HUMAN NECESSITIES
    • A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00—Radiation therapy
    • A61N2005/002—Cooling systems
    • A—HUMAN NECESSITIES
    • A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00—Radiation therapy
    • A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N2005/1085—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy characterised by the type of particles applied to the patient
    • A61N2005/1087—Ions; Protons
    • A—HUMAN NECESSITIES
    • A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00—Radiation therapy
    • A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N2005/1085—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy characterised by the type of particles applied to the patient
    • A61N2005/109—Neutrons
    • A—HUMAN NECESSITIES
    • A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00—Radiation therapy
    • A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N2005/1092—Details
    • A61N2005/1094—Shielding, protecting against radiation
    • A—HUMAN NECESSITIES
    • A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
    • A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
    • A61N5/00—Radiation therapy
    • A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
    • A61N2005/1092—Details
    • A61N2005/1098—Enhancing the effect of the particle by an injected agent or implanted device
    • H—ELECTRICITY
    • H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05H—PLASMA TECHNIQUE; PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS
    • H05H2242/00—Auxiliary systems
    • H05H2242/10—Cooling arrangements
    • H—ELECTRICITY
    • H05—ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05H—PLASMA TECHNIQUE; PRODUCTION OF ACCELERATED ELECTRICALLY-CHARGED PARTICLES OR OF NEUTRONS; PRODUCTION OR ACCELERATION OF NEUTRAL MOLECULAR OR ATOMIC BEAMS
    • H05H2277/00—Applications of particle accelerators
    • H05H2277/10—Medical devices
    • H05H2277/11—Radiotherapy

Abstract

The utility model provides a neutron capture therapy system sets up neutron shielding space and avoids or reduces the leakage of neutron as far as possible or to the radiation damage and the radiation pollution of other indoor equipment. The utility model discloses a neutron capture treatment system, including charged particle beam generation portion, beam transmission portion and neutron beam generation portion, charged particle beam generation portion produces the charged particle beam, beam transmission portion will the charged particle beam transmit extremely neutron beam generation portion, neutron beam generation portion produces the neutron beam for the treatment, the whole holding of neutron capture treatment system is in the building of concrete structure, form neutron shielding space in the building of concrete structure.

Description

Neutron capture therapy system
Technical Field
The utility model relates to a radiation irradiation system especially relates to a neutron capture treatment system.
Background
With the development of atomic science, radiation therapy such as cobalt sixty, linac, electron beam, etc. has become one of the main means of cancer therapy. However, the traditional photon or electron therapy is limited by the physical conditions of the radiation, and can kill tumor cells and damage a large amount of normal tissues in the beam path; in addition, due to the difference in the sensitivity of tumor cells to radiation, conventional radiotherapy is often ineffective in treating malignant tumors with relatively high radiation resistance, such as multiple glioblastoma multiforme (glioblastoma multiforme) and melanoma (melanoma).
In order to reduce the radiation damage of normal tissues around tumor, the target therapy concept in chemotherapy (chemotherapy) is applied to radiotherapy; for tumor cells with high radiation resistance, radiation sources with high Relative Biological Effect (RBE) are also actively developed, such as proton therapy, heavy particle therapy, neutron capture therapy, etc. Wherein, the neutron capture treatment combines the two concepts, such as boron neutron capture treatment, and provides better cancer treatment selection than the traditional radioactive rays by the specific accumulation of boron-containing drugs in tumor cells and the precise neutron beam regulation.
Various radioactive rays are generated in the radiation therapy process, for example, the boron neutron capture therapy process generates neutrons and photons with low energy and high energy, and the radioactive rays can cause damage to normal tissues of a human body to different degrees. Therefore, in the field of radiation therapy, it is an extremely important issue to reduce the radiation contamination to the external environment, medical staff or normal tissues of a patient while achieving effective treatment.
Therefore, a new technical solution is needed to solve the above problems.
SUMMERY OF THE UTILITY MODEL
In order to solve the above problem, the present invention provides a neutron capture treatment system, including charged particle beam generating part, beam transmission part and neutron beam generating part, the charged particle beam generating part produces the charged particle beam, beam transmission part will the charged particle beam transmit to neutron beam generating part, neutron beam generating part produces the neutron beam for treatment, the whole neutron capture treatment system is held in the building of concrete structure, form neutron shielding space in the building of concrete structure. Because a great amount of neutrons are generated in the neutron capture treatment process, especially near the neutron beam generating part, a neutron shielding space is arranged to avoid or reduce the leakage of neutrons or radiation damage and radiation pollution to other indoor equipment as much as possible.
Preferably, the neutron capture treatment system includes an irradiation chamber and a beam transmission chamber, the beam transmission chamber at least partially accommodates the beam transmission section, the neutron beam generation section is at least partially accommodated in a partition wall of the irradiation chamber and the beam transmission chamber, and the neutron shielding space is formed in the beam transmission chamber or the irradiation chamber.
As another preferable mode, a neutron shielding plate is provided on the concrete surface to form the neutron shielding space.
Further, the neutron shielding plate is arranged on the surface of the concrete through a supporting component, one side of the supporting component is connected with the concrete, and the other side of the supporting component is connected with the neutron shielding plate.
Further, the neutron shielding plate is a boron-containing PE plate; the supporting component is made of aluminum alloy; the supporting component is 2L-shaped plate-shaped elements which are connected with each other.
As another preferable mode, the neutron capture therapy system further comprises an auxiliary device, and a neutron shielding plate is arranged around the auxiliary device to form the neutron shielding space, so that radiation damage and radiation pollution of neutrons to the auxiliary device during the neutron capture therapy process are reduced.
Further, the charged particle beam generation part comprises an ion source and an accelerator, the ion source is used for generating charged particles, the accelerator accelerates the charged particles generated by the ion source to obtain charged particle beams with required energy, the neutron capture treatment system further comprises an accelerator chamber and a beam transmission chamber, the accelerator chamber at least partially accommodates the charged particle beam generation part, the beam transmission chamber at least partially accommodates the beam transmission part, and the auxiliary equipment is at least partially arranged in the accelerator chamber or the beam transmission chamber.
Further, an auxiliary equipment room is arranged for containing or surrounding the auxiliary equipment, and the auxiliary equipment room is at least partially constructed by a support assembly and the neutron shielding plate fixed on the support assembly.
Furthermore, the auxiliary equipment room comprises a door and a moving mechanism thereof, wherein the moving mechanism can open the door to allow an operator to enter the interior of the auxiliary equipment room, so that equipment maintenance and the like are facilitated.
Still further, the moving mechanism includes a guide rail and a slide bar, and the door is slidable in a horizontal direction along the guide rail by the slide bar.
Still further, the moving mechanism further comprises a lifting assembly and a pulley, the lifting assembly can lift the door in the vertical direction so as to arrange the pulley at the bottom of the door, and the door can slide in the horizontal direction through the pulley, so that labor is saved.
The utility model discloses a neutron capture treatment system sets up neutron shielding space and avoids or reduces the leakage of neutron or to the radiation damage and the radiation pollution of other indoor equipment as far as possible.
Drawings
Fig. 1 is a schematic structural view of a neutron capture treatment system according to an embodiment of the present invention;
fig. 2 is a block schematic diagram of a cooling apparatus of a neutron capture therapy system according to an embodiment of the present invention;
FIG. 3 is a schematic block diagram of the external circulation device of FIG. 2;
FIG. 4 is a schematic block diagram of the internal circulation device of FIG. 2;
fig. 5 is a block schematic diagram of an insulating gas charge recovery apparatus of a neutron capture therapy system according to an embodiment of the present invention;
fig. 6 is a schematic plan view of a neutron capture treatment system according to an embodiment of the present invention;
FIG. 7 is a schematic view of a partition wall between the control chamber and the irradiation chamber in FIG. 6;
fig. 8a and b are schematic layout diagrams of a neutron shielding plate and a support component, which are disposed on a side facing the beam transmission chamber of a partition wall of the irradiation chamber and the beam transmission chamber of the neutron capture treatment system according to an embodiment of the present invention, wherein 8a is a schematic layout diagram of the neutron shielding plate, and 8b is a schematic layout diagram of the support component;
FIG. 9 is a schematic view of the neutron shield and the support assembly of FIGS. 8a and b;
fig. 10 is a schematic view of an auxiliary equipment room disposed in a beam transmission chamber of a neutron capture therapy system according to an embodiment of the present invention;
fig. 11 is a schematic view of a treatment table positioning device of a neutron capture treatment system according to an embodiment of the present invention;
FIG. 12 is a schematic view of FIG. 11 in another orientation;
fig. 13 is a block diagram of a treatment table positioning device and a control device thereof of the neutron capture treatment system according to the embodiment of the present invention;
FIG. 14 is a schematic view of one embodiment of a slide rail cover of the treatment table positioning device of FIG. 11;
FIG. 15 is a schematic view of another embodiment of a slide rail cover of the treatment table positioning device of FIG. 11;
FIG. 16 is a schematic view of one embodiment of a robotic arm sheath of the treatment table positioning device of FIG. 11;
fig. 17 is a schematic layout view of a threading tube and a support frame of a neutron capture therapy system according to an embodiment of the present invention;
fig. 18 is a schematic view of an annular shield of a neutron capture therapy system in an embodiment of the invention.
Detailed Description
Embodiments of the present invention will be described in further detail with reference to the accompanying drawings so that those skilled in the art can implement the embodiments with reference to the description.
Referring to fig. 1, the neutron capture therapy system in the present embodiment is preferably a boron neutron capture therapy system 100, and the boron neutron capture therapy system 100 is a device for cancer therapy using boron neutron capture therapy. The boron neutron capture therapy is used for treating cancer by irradiating the irradiated body 200 injected with boron (B-10) with a neutron beam N, wherein the irradiated body 200 is administered or injected with a boron (B-10) drug, the boron drug is selectively accumulated in the tumor cells M, and then the boron (B-10) drug has a high capture cross section for thermal neutrons due to the characteristic of the boron (B-10) drug 10 B(n,α) 7 Li neutron capture and nuclear fission reaction generation 4 He and 7 li two heavily charged particles. The average Energy of the two charged particles is about 2.33MeV, and the particles have high Linear Energy Transfer (LET) and short-range characteristics, the Linear Energy Transfer and the range of the alpha short particles are 150 keV/mum and 8μm respectively, and 7 the Li-heavily-charged particles are 175 keV/mum and 5μm, and the total range of the two particles is about equal to the size of a cell, so that the radiation damage to organisms can be limited at the cell level, and the aim of locally killing tumor cells can be achieved on the premise of not causing too much damage to normal tissues.
The boron neutron capture therapy system 100 includes a beam generation apparatus 10 and a therapy table 20, and the beam generation apparatus 10 includes a charged particle beam generation unit 11, a beam transport unit 12, and a (first) neutron beam generation unit 13. The charged particle beam generating unit 11 generates a charged particle beam P such as a proton beam; a beam transport unit 12 that transports the charged particle beam P to a neutron beam generation unit 13; the neutron beam generating unit 13 generates a therapeutic neutron beam N and irradiates the object 200 on the treatment table 20.
The charged particle beam generating section 11 includes an ion source 111 and an accelerator 112, the ion source 111 being for generating charged particles such as H - Protons, deuterons, etc.; the accelerator 112 accelerates charged particles generated by the ion source 111 to obtain a charged particle beam P, such as a proton beam, of a desired energy.
The neutron beam generating unit 13 includes a target T, a beam shaper 131, and a collimator 132, and the charged particle beam P generated by the accelerator 112 is irradiated to the target T through the beam transport unit 12 to react with the target T to generate neutrons, and the generated neutrons pass through the beam shaper 131 and the collimator 132 in order to form a neutron beam N for treatment and are irradiated to the irradiation target 200 on the treatment table 20. The target T is preferably a metal target. According to the required neutron yield and energyThe energy and current of the charged particles and the physical and chemical properties of the metal target are accelerated to select the appropriate nuclear reaction, which is often discussed as 7 Li(p,n) 7 Be and 9 Be(p,n) 9 b, both reactions are endothermic. The energy thresholds of the two nuclear reactions are 1.881MeV and 2.055MeV respectively, because the ideal neutron source for boron neutron capture treatment is epithermal neutrons with keV energy level, theoretically if a metallic lithium target is bombarded by protons with energy only slightly higher than the threshold, neutrons with relatively low energy can Be generated, and can Be used clinically without too much slowing treatment, however, the proton interaction cross section of the two targets of lithium metal (Li) and beryllium metal (Be) and the threshold energy is not high, and in order to generate enough neutron flux, protons with higher energy are usually selected to initiate the nuclear reaction. An ideal target should have the characteristics of high neutron yield, neutron energy distribution generated close to the hyperthermic neutron energy region (described in detail below), not too much intense penetrating radiation generation, safety, cheapness, easy operation, and high temperature resistance, but practically no nuclear reaction meeting all the requirements can be found. As is well known to those skilled in the art, the target T may Be made of a metal material other than Li and Be, for example, Ta or W, an alloy thereof, or the like. The accelerator 10 may be a linear accelerator, a cyclotron, a synchrotron, a synchrocyclotron.
The beam shaper 131 can adjust the beam quality of the neutron beam N generated by the action of the charged particle beam P and the target T, and the collimator 132 is used for converging the neutron beam N, so that the neutron beam N has high targeting performance in the treatment process. The beam shaper 131 further includes a reflector 1311, a retarder 1312, a thermal neutron absorber 1313, a radiation shield 1314 and a beam outlet 1315, neutrons generated by the action of the charged particle beam P and the target T have a wide energy spectrum, and besides the epithermal neutrons meet the treatment requirement, the content of neutrons and photons of other types needs to be reduced as much as possible to avoid damage to operators or irradiated bodies, so that the fast neutrons (greater than 40keV) in the neutrons from the target T need to be adjusted to an epithermal neutron energy region (0.5eV-40keV) through the retarder 1312 and the thermal neutrons (less than 0.5eV) are reduced as much as possible, and the retarder 312 has a large fast neutron action cross section and is intercepted by the epithermal neutronsMade of a small material, in this embodiment the retarder 1312 is made of D 2 O、AlF 3 、Fluental、 CaF 2 、Li 2 CO 3 、MgF 2 And Al 2 O 3 At least one of (a); the reflector 1311 surrounds the retarder 1312, reflects neutrons diffused to the periphery through the retarder 1312 back to the neutron beam N to improve the utilization rate of the neutrons, and is made of a material having a strong neutron reflection capability, in this embodiment, the reflector 1311 is made of at least one of Pb and Ni; the thermal neutron absorber 1313 is arranged at the rear part of the retarder 1312 and is made of a material with a large cross section with the thermal neutrons, in the embodiment, the thermal neutron absorber 1313 is made of Li-6, and the thermal neutron absorber 1313 is used for absorbing the thermal neutrons penetrating through the retarder 1312 so as to reduce the content of the thermal neutrons in the neutron beam N and avoid excessive dose caused by shallow normal tissues during treatment, it can be understood that the thermal neutron absorber can also be integrated with the retarder, and the material of the retarder contains Li-6; the radiation shield 1314 is used for shielding neutrons and photons leaking from a portion outside the beam outlet 1315, and the material of the radiation shield 1314 includes at least one of a photon shielding material and a neutron shielding material, and in this embodiment, the material of the radiation shield 1314 includes lead (Pb) which is the photon shielding material and Polyethylene (PE) which is the neutron shielding material. It will be appreciated that the beam shaper 131 may have other configurations as long as the desired hyperthermal neutron beam for the treatment is obtained. The collimator 132 is disposed behind the beam outlet 1315, and the hyperthermo neutron beam emitted from the collimator 132 irradiates the irradiated object 200, and is slowed down to be thermal neutrons to reach the tumor cells M after passing through a shallow normal tissue, it is understood that the collimator 132 may be eliminated or replaced by another structure, and the neutron beam directly irradiates the irradiated object 200 after exiting from the beam outlet 1315. In this embodiment, a radiation shielding device 30 is further disposed between the irradiated object 200 and the beam outlet 1315 to shield the beam coming out of the beam outlet 1315 from the normal tissue of the irradiated object, but it should be understood that the radiation shielding device 30 may not be disposed. The target T is disposed between the beam delivery part 12 and the beam shaper 131, the beam delivery part 12 having a transport tube C for accelerating or transporting the charged particle beam P, in this embodiment, the transport tube C is along the charged particlesThe beam P extends into the beam shaper 131 and passes through the reflector 1311 and the retarder 1312 in sequence, and the target T is arranged in the retarder 1312 at the end of the transport tube C for better neutron beam quality. It will be appreciated that the target may be arranged otherwise and may be movable relative to the accelerator or beam shaper to facilitate target exchange or to enable the charged particle beam to interact homogeneously with the target.
The boron neutron capture therapy system 100 further includes an auxiliary device 14, and the auxiliary device 14 may include any auxiliary device for providing a precondition for the operations of the charged particle beam generation section 11, the beam delivery section 12, and the neutron beam generation section 13. In one embodiment, the auxiliary equipment 14 includes a cooling device 141, an air compressing device for providing compressed air, an insulating gas charging recovery device 142, a vacuum pump 143 for providing a vacuum environment, and the like, which is not limited in this respect.
The cooling apparatus 141 can be used for waiting for cooling of the cooling module CP by the charged particle beam generating unit 11, the target T, and the other auxiliary equipment 14, thereby improving the service life of the apparatus. The cooling medium of the cooling device 141 may be soft water, and the water pipe is not easy to scale during the cooling process, thereby affecting the heat exchange efficiency, especially in the case that the heat exchange part adopts a copper pipe, if the hardness is less than 60 mg/L; when used for cooling the charged particle beam generating unit 11 and the target T, the cooling medium must have extremely low electrical conductivity, for example, the electrical conductivity of the cooling medium is less than 10 μ S/cm, in order to meet the use requirements under high voltage conditions, prevent the occurrence of leakage current under high voltage conditions, and prevent interference with the generation of the charged particle beam. In the embodiment, two sets of cooling equipment are arranged, wherein one set adopts soft water with the hardness of less than 17 mg/L; one set adopts deionized water, and the conductivity is 0.5-1.5 muS/cm; it will be appreciated that other types of cooling media may also be employed.
As shown in fig. 2, the cooling apparatus 141 includes an external circulation device 1411, an internal circulation device 1412 and a heat exchanger 1413; the internal circulation device 1412 delivers a cooling medium (such as soft water or deionized water) to the to-be-cooled module CP for absorbing heat, then delivers the cooling medium heated by absorbing heat to the heat exchanger 1413 for heat exchange with the chilled water delivered to the heat exchanger 1413 by the external circulation device 1411, and delivers the cooling medium cooled by cooling to the to-be-cooled module CP for absorbing heat, and the above-mentioned steps are repeated; the external circulation device 1411 can continuously supply chilled water to the heat exchanger 1413 and recover the chilled water heated by absorbing heat. The external circulation device 1411 is disposed outdoors, i.e., outside a building (described in detail below) that houses the boron neutron capture therapy system 100, to discharge heat to the atmosphere, in this embodiment, on the roof of the building; the internal circulation device 1412 and the heat exchanger 1413 are disposed indoors, i.e., inside a building housing the boron neutron capture therapy system 100, to absorb heat of the component CP to be cooled; it will be appreciated that other arrangements are possible, such as placing the heat exchanger outdoors.
As shown in fig. 3, the external circulation device 1411 may include a heat sink unit 1411a, a first pump 1411b, a first control device 1411c for controlling the heat sink unit 1411a and the first pump 1411b, and the like, and the chilled water having absorbed heat and warmed up and coming out of the heat exchanger 1413 is delivered to the heat sink unit 1411a for cooling, the chilled water is pressurized and delivered to the heat exchanger 1413 by the first pump 1411b, and the first control device 1411c controls delivery of the chilled water. As shown in fig. 4, the internal circulation device 1412 may include a filter 1412a, a second pump 1412b, a second control device 1412c for controlling the filter 1412a and the second pump 1412b, one end of the internal circulation device 1412 is connected to the component CP to be cooled, the other end of the internal circulation device 1412 is connected to the heat exchanger 1413, the cooling medium absorbs heat of the component CP to be cooled at the end thereof, and then is pressurized by the second pump 1412b and sent to the heat exchanger 1413 to exchange heat with the chilled water, the cooling medium after being cooled and cooled is filtered by the filter 1412a and then sent to the interior of the component CP to be cooled to exchange heat, and the second control device 1412c controls the transportation of the cooling medium. When the cooling medium is deionized water, the conductivity of the cooling medium is continuously increased due to various factors in the circulation process, the conductivity of the cooling medium is maintained to meet the requirement through the filter, and a conductivity sensor (not shown) can be arranged to detect the conductivity of the cooling medium at the outlet of the filter 1412a to ensure the requirement is met. In the present embodiment, the heat exchanger 1413 is also controlled by the first control device 1411c, but it is understood that a separate control device may be provided or the second control device 1412c may control the heat exchanger.
The internal circulation device 1412 may also include a voltage regulation loop 1412d and be controlled by a second control device 1412 c. In one embodiment, the pressure stabilizing circuit 1412d may include a buffer tank, a nitrogen tank, a pressure sensor, etc. the pressure sensor may detect the pressure in the nitrogen tank, and when the pressure is smaller than a set value, the buffer tank may be replenished with nitrogen to increase the pressure, so as to ensure positive pressure in the system and prevent air from entering the system. The external circulation device 1411 and the internal circulation device 1412 may further include a chilled water replenishing circuit 1411d and a cooling medium replenishing circuit 1412e respectively and are controlled by the first and second control devices 1411c and 1412c respectively, and when the chilled water/cooling medium is insufficient, an alarm is given and the chilled water/cooling medium replenishing circuit 1411 d/cooling medium replenishing circuit 1412e is used for replenishing; the external circulation device 1411 and the internal circulation device 1412 can also comprise temperature sensors, regulating valves, pressure sensors and the like, and are controlled by the first control device 1411c and the second control device 1412 c; it is understood that the cooling device 141 may have other configurations.
The accelerator 112 includes an accelerator high voltage power supply (ELV)1121 for supplying acceleration energy, and in order to prevent breakdown of electronic components inside the accelerator high voltage power supply 1121, it is necessary to supply an insulating gas (such as an insulating gas disposed inside the housing of the accelerator high voltage power supply 1121) to the accelerator high voltage power supply 1121, and the insulating gas may be SF 6 It will be appreciated that other insulating gases may be used. The insulating gas is supplied to the accelerator high-voltage power supply 1121 through the insulating gas inflation recovery device 142 or recovered from the accelerator high-voltage power supply 1121, so that the insulating gas can be recovered when the relevant equipment is maintained and overhauled, and the utilization rate of the insulating gas is improved.
Referring to FIG. 5, the insulation gas charge recovery device 142 includes a gas source 1421 (e.g., containing SF) 6 Cylinder) reservoir 1422 connected to a gas source 1421 and an accelerator high voltage power supply 1121, respectively. In the initial state, the gas source 1421 contains an insulating gas in a container; then, the insulating gas is firstly inflated into the storage container 1422 from the container of the gas source 1421, and then the insulating gas is inflated into the ELV from the storage container 1422, so that the ELV can start to work normally; when the ELV needs to be opened for maintenance, inspection, or the like, the insulating gas is recovered from the ELV into the storage container 1422 for maintenanceAfter the maintenance is finished, the insulating gas is charged into the ELV from the storage container 1422; when the storage vessel 1422, the pipes, the elements, etc. of the insulating gas inflation recovery apparatus 142 need to be maintained or have a fault and need to be repaired, the insulating gas can be refilled from the storage vessel 1422 into the gas source 1421 to return to the initial state, and after the maintenance and the repair are finished, the inflation is performed again.
The insulating gas aeration recovery apparatus 142 may further include a filtering device 1423 and a drying device 1424 disposed between the storage vessel 1422 and the ELV, the filtering device 1423 removes oil, large particle impurities, and the like in the recovered insulating gas to maintain the purity of the insulating gas when the insulating gas is recovered from the ELV into the storage vessel 1422, and the drying device 1424 removes most of water molecules in the recovered insulating gas to maintain the gas in a relatively dry state. The filtering device 1423 may be a filter screen, and the drying device 1424 may be electrically heated for drying, or may be dried or filtered by other methods; in this embodiment, the insulating gas passes through the filtering device 1423 and then passes through the drying device 1424, it can be understood that the insulating gas may be dried and then filtered, and the drying device 1423 and the filtering device 1424 may also be integrated; a moisture detecting element, an oil detecting element, or an impurity detecting element may be further included.
The filling recovery apparatus 142 may further include a refrigerating device 1425 and a compressing device 1426 disposed between the container of the gas source 1421 and the storage container 1422, wherein when the insulating gas is filled from the storage container 1422 into the container of the gas source 1421, the refrigerating device 1425 converts the insulating gas into a liquid state, and the compressing device 1426 compresses the gaseous or liquid insulating gas to fill the container of the gas source 1421, it is understood that the sequence of the refrigerating device 1425 and the compressing device 1426 is not limited, and the refrigerating device 1425 and the compressing device 1426 may be integrated.
The insulating gas charge recovery apparatus 142 may also include a vacuum pump that is activated to evacuate the storage vessel 1422, pipes, components, etc. of the insulating gas charge recovery apparatus 142 to evacuate the air within the apparatus prior to charging. The accelerator high voltage power supply 1121 may also be provided with a vacuum pump 143 to evacuate the ELV to exhaust air prior to inflation and ELV operation. The insulating gas charge recovery device 142 may also include a compressor to power the charging, recovery (recharge) process described above. The insulating gas inflation recovery apparatus 142 may further include a valve, a vacuum degree detection element, a pressure detection element, and the like, and controls the inflation and recovery (recharge) processes. It will be appreciated that the insulating gas charge recovery device 142 may also have other configurations.
Referring to fig. 6, the boron neutron capture therapy system 100 is integrally housed in a concrete-structured building, and specifically includes a (first) irradiation chamber 101, an accelerator chamber 102, and a beam transport chamber 103, wherein an object 200 to be irradiated on a treatment table 20 is subjected to a therapy by irradiation of a neutron beam N in the irradiation chamber 101, the accelerator chamber 102 at least partially houses a charged particle beam generating unit 11 (e.g., an ion source 111 and an accelerator 112), the beam transport chamber 103 at least partially houses a beam transport unit 12, the neutron beam generating unit 13 is at least partially housed in a partition wall W1 between the irradiation chamber 101 and the beam transport chamber 103, and an auxiliary device 14 is at least partially disposed in the accelerator chamber 102 or the beam transport chamber 103.
The boron neutron capture therapy system 100 may further include a second irradiation chamber 101 ', the beam generating apparatus 10 may further include a second neutron beam generating unit 13 ' corresponding to the second irradiation chamber 101 ', and the beam transmitting unit 12 may include a beam direction switching assembly 121, and the beam transmitting unit 12 may selectively transmit the charged particle beam P generated by the charged particle beam generating unit 11 to the first neutron beam generating unit 13 or the second neutron beam generating unit 13 ' through the beam direction switching assembly 121, so as to emit a beam into the first irradiation chamber 101 or the second irradiation chamber 101 '. It should be understood that the neutron beam N irradiated into the second irradiation chamber 101 ' may be used for the treatment of the irradiation of the neutron beam N of another irradiated object on the treatment table 20 ' in the second irradiation chamber 101 ', and may also be used for the sample detection, etc., which is not limited by the present invention.
It should be understood that other configurations of the beam generating apparatus 10 are possible. If there is a third irradiation chamber, a third neutron beam generation part corresponding to the third irradiation chamber may be added, and the number of the neutron beam generation parts corresponds to the number of the irradiation chambers, the embodiment of the present invention is not particularly limited to the number of the neutron beam generation parts; it is understood that the beam generating apparatus may include a plurality of charged particle beam generating units, and may be configured to transmit the charged particle beam generating units to the respective neutron beam generating units, thereby simultaneously generating and irradiating a plurality of neutron beams in a plurality of irradiation chambers.
In an embodiment of the present invention, the beam direction switching module 121 includes a deflection magnet (not shown) for deflecting the charged particle beam P, and the beam is guided to the first irradiation chamber 101 if the deflection magnet corresponding to the first irradiation chamber 101 is turned on, which is not particularly limited by the present invention. The boron neutron capture therapy system 100 may further include a beam dump 40 that collects a beam when the beam is not needed, checks the output of the charged particle beam P before therapy, and the like, and the beam direction switching unit 121 may guide the charged particle beam P to the beam dump out of a normal trajectory.
The boron neutron capture therapy system 100 may also include a preparation room (not shown), a control room 104, and other spaces (not shown) for auxiliary therapy. Each irradiation room may be provided with a preparation room for performing preparation works such as fixing the irradiated object to the treatment table before irradiation treatment, simulation positioning of the irradiated object, simulation of a treatment plan, and the like. The control room 104 is used for controlling the accelerator, the beam delivery unit, the treatment table, etc. to control and manage the whole irradiation process, and the manager can monitor a plurality of irradiation rooms at the same time in the control room.
Since the boron neutron capture therapy is continuously administered during the boron neutron capture therapy, the boron neutron capture therapy system 100 further includes a medicament injection device 50 for injecting a boron (B-10) -containing medicament into the irradiated object 200 during the irradiation therapy. The drug injection device 50 includes a drug passing assembly 51 disposed between a drug control chamber (in this embodiment, a control chamber 104) and the irradiation chamber 101, the drug passing assembly 51 including a drug passing piece 511 for injecting a boron (B-10) -containing drug and a receiving piece 512 for at least partially receiving the drug passing piece 511, the irradiation chamber 101 having a partition wall W2 spaced from the drug control chamber, the receiving piece 512 being disposed in the partition wall W2 and forming a passage for the drug passing piece 511 through the partition wall W2, the receiving piece 512 further supporting the drug passing piece 511. In this embodiment, the receiving member 512 is fixedly disposed in the dividing wall W2, such as by interference fit, it being understood that other arrangements may be used. The receiving member 512 facilitates the passage of the agent passage member 511 on the one hand, and partitions the concrete wall on the other hand, preventing dust and the like from contaminating the agent passage member 511. The drawings show only a device for injecting a boron drug into the object 200 in the first irradiation chamber 101, but it is to be understood that the same drug injection device 50 may be used for injecting a boron drug into an object in another irradiation chamber.
The chemical injection device 50 may further include a chemical containing mechanism 52 and a chemical control mechanism 53, the chemical containing mechanism 52 and the chemical control mechanism 53 may be provided in the chemical control chamber and control injection of the boron-containing (B-10) drug of the irradiated object 200 may be performed in the chemical control chamber, and neutron radiation in the irradiation chamber 101 may be prevented from affecting the chemical containing mechanism 52 and the chemical control mechanism 53, such as causing electronic components in the chemical control mechanism 53 to fail to operate normally or to react with the boron-containing drug contained in the chemical containing mechanism 52. The chemical passing member 511 is connected to the chemical containing mechanism 52 and injects the boron (B-10) containing drug into the irradiated body 200 through the chemical control mechanism 53. The chemical holding mechanism 52 may be an infusion bag or an infusion bottle, and the chemical control mechanism 53 may be connected to the chemical passing member 511 and control the flow of the boron (B-10) containing chemical in the chemical passing member 511, for example, a pump may be used to provide the motive force for the flow of the liquid (boron (B-10) containing chemical), and may also control the flow rate, and may also have functions of detection, alarm, and the like. The medicine passage member 511 may be a disposable infusion tube or the like, and includes a needle inserted into the irradiated body, a needle protector, a hose, a connector connected to the medicine accommodating section 52, and the like. The agent passage 511 may also be at least partially made of neutron shielding material, such as a needle, a hose portion disposed in the irradiation chamber 101, and may reduce the effect of neutron radiation from the irradiation chamber on the boron-containing drug in the agent passage 511.
Referring to fig. 7, in the present embodiment, the accommodating member 512 is disposed in the through hole 513 of the partition wall W2 in the thickness direction, the central axis X of the through hole 513 intersects with the ground and a plane perpendicular to the ground in the thickness direction of the partition wall W2, that is, the through hole 513 passes through the partition wall W2 in a manner inclined in both the horizontal and vertical directions to reduce radiation leakage, and the central axis X of the through hole 513 is a straight line. In one embodiment, the distance D1 from the center of the through hole 513 on the first sidewall S1 of the partition wall W2 facing the control chamber 104 to the ground is greater than the distance D2 from the center of the through hole 513 on the second sidewall S2 of the partition wall W2 facing the irradiation chamber 101 to the ground; such as a distance from the center of the through-hole 513 to the ground in the direction of the partition wall W2 from the control room 104 to the irradiation room 101. In this embodiment, the accommodating member 512 is a tubular member disposed in the through hole 513, an outer wall of the tubular member is engaged with an inner wall of the through hole, and the shape of the inner wall of the tubular member is not limited, but it is to be understood that the accommodating member 512 may be a box body provided with a hole through which the medicine passing member 511 passes, and may also be 1 or more than one snap fasteners.
The containment member 512 is PVC, and the product after neutron irradiation has no or very low radioactivity, and thus the generation of secondary radiation is reduced, but it is understood that other materials that do not have radioactivity of the product after neutron irradiation, have low radioactivity of the product after neutron irradiation, or have a short half-life of the radioisotope generated after neutron irradiation may be used. The receiving members 512 and the through-holes 513 may be provided at least 2 per partition wall, for backup when one of them is clogged or otherwise problematic.
The process of injecting boron (B-10) containing medicine during irradiation treatment: before irradiation treatment is started, an appropriate medicament passing element 511 is selected and the medicament passing element 511 is connected with the medicament containing mechanism 52 and the medicament control mechanism 53, the medicament passing element 511 is placed in an appropriate position in the irradiation chamber 101 through the containing element 512, after the irradiated object 200 is positioned in the irradiation chamber 101 and a treatment plan is determined, an operator in the medicament control chamber opens the medicament control mechanism 53, a doctor in the irradiation chamber 101 removes a needle protection sleeve and inserts a needle into the irradiated object 200 or inserts an irradiated object 200 before the irradiated object 200 is positioned, and after the doctor leaves the irradiation chamber 101, the operator controls the irradiated object to be irradiated in the control chamber 104 and controls the injection of boron (B-10) containing medicament. It is understood that the same drug injection device 50 (except the containing member 512) may be used for injecting the boron-containing (B-10) drug before the irradiation treatment, the drug passage member 511 is disconnected before the irradiation chamber 101 is entered, for example, the needle is pulled out or an indwelling needle is used, and the drug passage member 511 is reconnected or replaced with a new drug passage member 511 after the irradiation chamber 101 is entered; the boron-containing (B-10) medicine injection before irradiation or the related control of the boron-containing (B-10) medicine injection during irradiation treatment can also be carried out in the preparation chamber, and the preparation chamber is used as a medicine control chamber. It is to be understood that the agent injection device 50 may also be applied to other types of neutron capture therapy systems, and that boron (B-10) containing drugs may be substituted for other agents.
Because a great amount of neutrons are generated in the neutron capture treatment process, especially near the target T generating the neutrons, the leakage of the neutrons needs to be avoided as much as possible. In one embodiment, the concrete forming at least a portion of the space (e.g., beam transport chamber 103, irradiation chambers 101, 101') is concrete with neutron shielding material added thereto, such as boron-containing barite concrete, to form the neutron shielding space. In another embodiment, a neutron shielding plate 60, such as a boron-containing PE plate, is disposed on a concrete surface in a room (e.g., ceiling, floor, wall of the beam transmission room 103, irradiation rooms 101, 101') to form a neutron shielding space, and it is understood that the neutron shielding plate 60 may be closely attached to the concrete surface or may be spaced apart from the concrete surface by a predetermined distance; the neutron shielding plate can be arranged on the surface of the whole concrete wall, or can be arranged on only partial areas, for example, the neutron shielding plate is arranged on the floor surface of the central area of the irradiation chamber, the neutron shielding plate is not arranged on the floor surface of the inlet area of the irradiation chamber, and the two areas are connected through a ramp to form a height difference. The neutron shielding plate 60 is disposed on the concrete surface through the supporting assembly 61, as shown in fig. 8a and b, the layout of the neutron shielding plate 60 and the supporting assembly 61 disposed on the side of the dividing wall W1 of the irradiation chamber 101 and the beam transmission chamber 103 facing the beam transmission chamber 103 is illustrated, fig. 9 illustrates the fixing manner of the neutron shielding plate 60 and the supporting assembly 61, the neutron shielding plate 60 is formed by combining a plurality of blocks, the long strip-shaped supporting assemblies 61 are disposed on the concrete of the dividing wall W1 at a preset interval through expansion bolts, each block of the neutron shielding plate 60 is sequentially fixed at a corresponding position on the supporting assembly 61 through screws, that is, one side of the supporting assembly 61 is connected with the concrete, and the other side of the supporting assembly 61 is connected with the neutron shielding plate 60. In this embodiment, the supporting assembly 61 is 2L-shaped plate elements connected by bolts, and it is understood that the supporting assembly 61 and the fixing manner may have other arrangements, for example, the supporting assembly 61 is at least partially constructed by a profile, and the neutron shielding plate 60 may be directly fixed on the concrete surface; the neutron shielding plate 60 may be provided on a side wall of the housing groove for housing the neutron beam generating unit 13 in the partition wall W1.
In order to reduce radiation damage and radiation pollution of neutrons in the neutron capture treatment process to other indoor equipment, such as the auxiliary equipment 14, a neutron shielding plate 60 can be arranged around the auxiliary equipment 14 to form a shielding space; referring to fig. 10, in one embodiment, an auxiliary equipment room 105 is provided in the beam delivery chamber 103 for accommodating or enclosing the auxiliary equipment 14 and the like. The auxiliary equipment room 105 is at least partially constructed by a support assembly 61 and a neutron shielding plate 60 (only a part of the neutron shielding plate is illustrated in the figure) fixed on the support assembly 61, in the embodiment, the auxiliary equipment room 105 is arranged at the corner of the beam transmission chamber 103 and shares part of the wall and the floor of the beam transmission chamber 103, the support assembly 61, the neutron shielding plate 60 fixed on the support assembly 61 and the part of the wall and the floor of the beam transmission chamber 103 jointly form a space for accommodating and surrounding the auxiliary equipment 14, that is, the neutron shielding plate 60 fixed on the support assembly 61 forms three faces of a cubic accommodating space, and the part of the wall and the floor of the beam transmission chamber 103 form the other three faces of the cubic accommodating space. The auxiliary equipment room 105 may further have a door 1051 and a moving mechanism 1052 thereof, the moving mechanism 1052 is used for opening the door 1051 for an operator to access the inside of the auxiliary equipment room 105 during equipment maintenance, for example, and the moving mechanism 1052 includes a guide rail 1052a and a slide bar 1052b, the door 1051 can slide along the guide rail 1052a in a horizontal direction through the slide bar 1052b, in this embodiment, the door 1051 is configured by a door support assembly 1051a and a neutron shielding plate 60 fixed on the door support assembly 1051a, the slide bar 1052b is fixedly connected to the door support assembly 1051a, for example, arranged at the top end of the door 1051, and the guide rail 1052a is fixedly connected to the support assembly 61 of the auxiliary equipment room 105, it is understood that the moving mechanism 1052 may have other configurations, for example, the door is rotatable. The moving mechanism 1052 may further include a lifting assembly 1052c and a pulley 1052d, the lifting assembly 1052c for lifting the door 1051 in a vertical direction to place the pulley 1052d at the bottom of the door 1051 so that the door 1051 can slide in a horizontal direction by means of the pulley 1052 d; in this embodiment, the lifting assembly 1052c is configured as a jack 1052e and an attachment plate 1052f secured to the door support assembly 1051a, and the jack 1052e is acted upon the attachment plate 1052f to cause the door 1051 to slide along the rail 1052a in a vertical direction via the slide bar 1052b to raise the door 1051 in the vertical direction, although it is understood that the lifting assembly 1052c may have other configurations. The auxiliary equipment room 105 may further include a fixing member 1053 for fixing the door 1051 and the auxiliary equipment room 105 together when the door 1051 is closed, for reinforcing the fixing and preventing the lateral turning, in this embodiment, the fixing member 1053 is configured as an L-shaped plate, and both side plates of the L-shaped plate are fixed to the door supporting assembly 1051a and the supporting assembly 61 of the auxiliary equipment room 105 or the child shielding plate 60, respectively. The auxiliary equipment room 105 may also have an opening 1054 for the passage of pipes, cables, etc., in this embodiment, the opening 1054 is located at a corner near the wall and floor. The support members 61 and the door support members 1051a of the auxiliary equipment room 105 are constructed of interconnected profiles, it being understood that the auxiliary equipment room 105 may have other configurations and that the auxiliary equipment room may be provided in other spaces.
The neutron shielding plate 60 is a boron-containing PE plate, and the materials of the support assembly 61, the door support assembly 1051a, the guide rail 1052a, the slide bar 1052b, and the fixing member 1053 are aluminum alloys, it can be understood that the neutron shielding plate 60 can also be made of other neutron shielding materials, and can have different thicknesses at different positions according to the needs, and the surface can be provided with other decoration or be provided with other elements through grooves; the aluminum alloy can be replaced by other materials which have certain strength and do not have radioactivity of products after being irradiated by neutrons, or have low radioactivity of products after being irradiated by neutrons, or have short half-life of radioactive isotopes generated after being irradiated by neutrons, such as carbon fiber composite materials or glass fiber composite materials.
With reference to fig. 11-13, a treatment table positioning device 70A and a shielding device 70B of the treatment table positioning device may be further disposed in the irradiation room 101, 101', the treatment table positioning device 70A includes a linear shaft 71a and a mechanical arm 72a, the mechanical arm 72a is disposed between the linear shaft 71a and the treatment table 20 for supporting and positioning the treatment table 20, and connects the treatment table 20 to the linear shaft 71a and enables the treatment table 20 and the mechanical arm 72a to translate together along the linear shaft 71 a. In the present embodiment, the linear shaft 71a is mounted to the ceiling of the irradiation chamber and the robot arm 72a extends generally toward the floor of the irradiation chamber, it being understood that the linear shaft 71a may be mounted to other surfaces, such as a wall or floor; the linear shaft 71a is configured as a slide rail 711a fixed to a ceiling and a support 712a coupled to the robot arm 72a, the support 712a sliding along the slide rail 711a, although it will be appreciated that other configurations are possible. The linear shaft 71a is directly fixed on the ceiling, and a linear shaft fixing mechanism such as a steel structure portal frame is not additionally arranged, so that the consumption of steel in an irradiation chamber is reduced, and the secondary radiation caused by neutron activation of the fixing mechanism is reduced. The robot arm 72a is a multi-axis robot arm connecting the support 712a and the treatment table 20, and includes a plurality of arm portions 721a (721 a').
Since the support 712a is connected with the mechanical arm 72a and slides along the sliding track 711a, the neutron shielding plate 60 arranged on the ceiling or other fixed surface needs to reserve a sliding space, which may cause the sliding track to be exposed and radiation to leak, and therefore, the shielding device 70B includes the sliding track cover 71B, and the sliding track cover 71B moves together with the support 712a to always cover the exposed part of the sliding track 711 a. The shielding device 70B further includes a mechanical arm sheath 72B surrounding at least one arm portion 721a (721 a') of the mechanical arm 72a, wherein the material of the mechanical arm sheath 72B is at least partially neutron shielding material to prevent the arm portion and metal components, electronic devices, etc. disposed in the mechanism of the arm portion from being damaged or deteriorated by neutron irradiation, such as boron-containing glass fiber composite, and it is understood that other shielding materials may be used.
The treatment table positioning device 70A may further include a drive mechanism 73a, and a treatment table control device 70C may be further provided in the irradiation room 101, 101' or the control room 104. The treatment table control device 70C is connected to the driving mechanism 73a and controls the movement of the linear shaft 71a and the robot arm 72a by controlling the driving mechanism 73a, and position information of the linear shaft 71a and the robot arm 72a can also be fed back to the treatment table control device 70C, and the driving mechanism 73a can be provided on the linear shaft 71a or the robot arm 72a, such as the support 712a or at least one arm portion 721 a.
The treatment table positioning device 70A may further include an anti-collision protection mechanism 74a, where the anti-collision protection mechanism 74a includes a sensor 741a, a sensor control unit 742a, and a human-machine interface 743a, and the sensor 741a is disposed on the arm sheath 72b, and it is understood that it may also be disposed between the arm sheath 72b and the arm 72 a. When the edge of the robot arm 72a or the robot arm sheath 72b contacts another object or another object reaches the set range of the sensor 741a, the sensor 741a is triggered to send a signal, the signal sent by the sensor 741a is transmitted to the sensor control component 742a and displayed on the hmi 743a, the sensor control component 742a transmits the received signal to the treatment table control device 70C to perform corresponding control, such as the treatment table control device 70C controls the driving mechanism 73a to stop driving the linear shaft 71a and the robot arm 72a, i.e., controls the treatment table 20 to stop moving. It can be understood that the sensor control component can also perform corresponding control according to the received signals; the operator can also manually control the driving mechanism to stop driving according to the display of the human-computer interface; instead of controlling the table to stop moving, other safety operations may be performed, such as performing a counter-movement before the collision. The sensor 741a may be a mechanical sensor, a photoelectric sensor, a radar sensor, an ultrasonic sensor, a laser range finder, or the like, and may be disposed at another position.
The linear shaft 71a and its driving mechanism 73a may be mounted to a fixed surface of the irradiation chamber 101, 101' by a fixing member or a supporting member (not shown), the fixing member or the supporting member may be configured of an aluminum profile, for example, a slide 711a is fixed to a ceiling by the fixing member, a support 712a and the driving mechanism 73a of the linear shaft 71a are fixed or supported to the ceiling by the supporting member, and a slide cover 71b is disposed between the support 712a and the neutron shielding plate 60 of the fixed surface of the linear shaft 71 a. As shown in fig. 14 and 15, in an embodiment, the slide rail cover 71b includes a first portion 711b and a second portion 712b, the first portion 711b and the second portion 712b each include a flat plate connected in sequence and are supported by a support 713b of the slide rail cover, one end of the first portion 711b and the second portion 712b close to the support 712a in the sliding direction a of the support 712a is fixedly connected with the support 712a through the connecting plates 7111b and 7121b, and the other end is fixedly connected with the support 713b, it is understood that the fixing manner may be screw connection, adhesion, and the like; the first part 711b and the second part 712b are sequentially connected with each other in a sliding manner (the first part 711b shown on the left side in fig. 14) or in a pivoting manner (the second part 712b shown on the right side in fig. 14), it is understood that other connection manners can be adopted between the plates, the connection manners are only schematically shown and different connection manners can be selected according to the needs of the first and second parts 711b and 712 b. The support 713b may be connected to and fixed to a fixing member or a support member of the linear shaft 71a and the driving mechanism 73a thereof, or may be directly fixed to a fixed surface, the support 713b is made of an aluminum alloy, the material of the slide rail cover 71b includes PE or other neutron shielding materials containing boron, the neutron shielding plate 60 covers the support 713b and shields the linear shaft 71a, the driving mechanism 73a of the linear shaft 71a, and the installation portion thereof together with the slide rail cover 71b (except for a portion where the support 712a penetrates through the neutron shielding plate 60), it can be understood that the aluminum alloy may be replaced by other materials having a certain strength, and the product irradiated by neutrons has no radioactivity, or the product irradiated by neutrons has low radioactivity, or the radioisotope half-life generated after being irradiated by neutrons is short; the support 713b may also be made of a neutron shielding material, in which case, the neutron shielding plate 60 may not cover the support 713b, but may be matched with the support 713b, and the neutron shielding plate 60, the support 713b, and the slide rail cover 71b together shield the linear shaft 71a, the driving mechanism 73a of the linear shaft 71a, and the installation portion thereof (except for the portion of the support 712a penetrating through the neutron shielding plate 60). During the movement of the seat 712a along the slide 711a, the first and second portions 711b, 712b of the slide cover 71b extend and retract, thereby reducing neutron leakage during the entire movement.
Referring to fig. 16, in the present embodiment, the robot arm sheath 72b surrounding the arm portion 721a includes first and second housings 721b, 722b, the first and second housings 721b, 722b are fixedly connected together and surround the arm portion 721a and a driving mechanism 73a (e.g., a motor, a circuit board, etc.) or a control mechanism (e.g., a sensor control unit 742a or a component of the treatment table control device 70C) provided in the arm portion 721 a. The first and second cases 721b and 722b are made of a glass fiber composite material containing boron, which has a certain strength, and the product irradiated with neutrons has no radioactivity or has a very low radioactivity, so that secondary radiation is prevented from being generated, and boron can absorb neutrons, thereby preventing the arm and metal parts, electronic components, and the like provided in the drive mechanism or control mechanism of the arm from being damaged or deteriorated by neutron irradiation. It is understood that the material of the first and second shells may also be other neutron shielding materials with certain strength.
In this embodiment, the arm protector 72b 'surrounding the arm portion 721 a' includes third and fourth housings 723b and 724b in addition to the first and second housings 721b and 722b, the third and fourth housings 723b and 724b are fixedly coupled together and surround the first and second housings 721b and 722b, and the sensor 741a is disposed between the first and third housings 721b and 723b and between the second and fourth housings 722b and 724 b. The number of the sensors 741a may be plural, and the sensors may be distributed around the arm portion 721 a. The first and second housings 721b, 722b are provided with a receiving cavity 725b for receiving the sensor 741a, the sensor 741a is disposed in the receiving cavity 725b and is interference-mounted between the first and third housings 721b, 723b and between the second and fourth housings 722b, 724b, specifically, a gap 726b is provided between the first and third housings 721b, 723b and between the second and fourth housings 722b, 724b, and the gap 726b is used for mounting the sensor 741 a. A power supply, a communication cable, and the like of the sensor 741a may be connected to the sensor control unit 742a through the gap 726b, or a through hole 727b (not shown) may be provided in the third and fourth housings 723b, 724b at a position corresponding to the sensor 741a, where the through hole 727b is used for the power supply, the communication cable, and the like of the sensor 741a to pass through. It is understood that other mounting arrangements for the sensor 741a are possible. In this embodiment, the sensor 741a is a pressure sensor, and the sensor 741a converts the pressure applied to the third and fourth housings 723b, 724b into a pressure signal, transmits the pressure signal to the sensor control component 742a, and displays a numerical value on the human-machine interface 743 a; when the pressure signal received by the sensor 741a exceeds the preset value, the pressure signal exceeding the preset value is preferentially transmitted to the sensor control component 742a and is displayed on the human-machine interface 743a, for example, by a light or sound alarm, the sensor control component 742a transmits the signal to the treatment table control device 70C, and controls the linear shaft 71a and the mechanical arm 72a to stop moving, or the operator manually stops moving the linear shaft 71a and the mechanical arm 72 a.
The third and fourth housings 723b and 724b are made of glass fiber resin composite material, have a certain strength, and the product after neutron irradiation has no radioactivity or very low radioactivity, so as to prevent secondary radiation from being generated. It is understood that the material of the third and fourth shells may be replaced by a boron-containing fiberglass composite material, that is, the shell at the outermost layer of the mechanical arm sheath 72b is made of a material capable of absorbing neutrons, so as to prevent metal components, electronic devices, and the like disposed in the driving mechanism or the control mechanism of the arm from being damaged or failed after being irradiated by neutrons, and the material of the first and second shells is not limited. The housing of the sensor 741a is made of aluminum alloy to avoid using conventional steel to generate radioactive isotope with long half-life, such as cobalt 60, to generate secondary radiation, and it can be understood that the aluminum alloy can be replaced by other materials with certain strength, and the product after neutron irradiation has no radioactivity or the product after neutron irradiation has low radioactivity, or the radioactive isotope generated after neutron irradiation has short half-life. It is understood that the sensor 741a may be disposed only between the first and third housings 721b, 723b or the second and fourth housings 722b, 724 b.
The first and second casings 721b, 722b and the third and fourth casings 723b, 724b may be fixedly connected by screws, welding, etc., the connecting member is made of aluminum alloy, has a certain strength, and the half-life of the radioactive isotope produced by the activation of the aluminum by the neutron is short, and the aluminum alloy may be replaced by other materials which have a certain strength, and the product irradiated by the neutron has no radioactivity or the product irradiated by the neutron has low activity or the half-life of the radioactive isotope produced by the irradiation of the neutron is short.
In this embodiment, the third and fourth housings 723b and 724b and the sensor 741a are provided on the arm portion 721 a' having a large movable range, and only the first and second housings 721b and 722b are provided on the arm portion 721a having a small movable range. It is to be understood that the third and fourth housings 723b and 724b and the sensor 741a may be provided in all the arm portions of the robot arm 72 a; the arm portion not provided with the driving mechanism 73a may be not provided with the arm protector 72b, and in this case, the arm portion is made of a material having a certain strength, in which the product irradiated with neutrons does not have radioactivity, in which the activity of the product irradiated with neutrons is low, or in which the half-life of the radioisotope generated after irradiation with neutrons is short, such as an aluminum alloy, or may be made of a neutron shielding material.
It is understood that the treatment table positioning device 70A may not include a linear axis, and in this case, the shielding device 70B does not include the slide rail cover 71B; the treatment table 20, the treatment table positioning device 70A, and the shielding device 70B of the treatment table positioning device may be provided in the preparation room as in the irradiation rooms 101 and 101'.
It will be appreciated that radiation shielding may also be provided for other alarm, monitoring, surveillance equipment, etc.
In order to realize the control of the operation and treatment processes of all the devices of the system, a power supply, a communication cable and a control cable are required to be arranged and reasonably arranged. Referring to fig. 17, a threading pipe 80A is disposed in the irradiation room 101, the control room 104 and the accelerator room 102, the threading pipe 80A is used for a cable to pass through and support the cable, the threading pipe 80A extends along the cable extending direction and is at least partially closed around the circumference of the cable extending direction, the cross-sectional shape of the threading pipe 80A perpendicular to the cable extending direction may be circular, polygonal, v-shaped, u-shaped, v-74, etc., and the threading pipe 80A is fixed on the wall or the floor or the ceiling by a connecting member (such as a bolt). In the present embodiment, the threading pipes 80A are disposed in the irradiation room 101, the control room 104 and the accelerator room 102 along the corners of the ceiling and the wall, and it is understood that the threading pipes 80A may be disposed at other positions or in other spaces, and the size of the threading pipes 80A may be designed according to the number of cables to be accommodated. The accelerator chamber 102 and the beam transport chamber 103 are provided with a support frame 80B, since the accelerator 112, the beam transport unit 12, the auxiliary equipment 14, and the like have a large number of power supply, communication, control cables, and liquid (e.g., cooling medium) or gas (e.g., insulating gas) pipelines, the support frame 80B is provided to be supported and guided, the support frame 80B has a supporting surface S for supporting the cables or the pipelines, the support frame 80B is fixed on the ground or the ceiling or other objects in a manner that the supporting surface S is parallel to the ground, or is fixed on the wall in a manner that the supporting surface 81B is perpendicular to the ground, and the support frame 80B may be provided in other spaces as needed. Only the support frame 80B provided along the beam transmitting portion 12 in the beam transmitting chamber 103 is illustrated, the support frame 80B is fixed to the floor surface in such a manner that the bearing surface S is parallel to the floor surface, the support frame 80B is configured by side plates 81B and a plurality of horizontal plates 82B connected between the side plates 81B at predetermined intervals, and the horizontal plates 82B form the bearing surface S. The threading pipe 80A and the support frame 80B are made of aluminum alloy; it is understood that the aluminum alloy may be replaced by other materials having a certain strength and having no radioactivity in the product after neutron irradiation or having a low activity in the product after neutron irradiation or having a short half-life of the radioisotope generated after neutron irradiation, such as 90 wt% or more of at least one element selected from C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti.
For the normal operation and safety requirements of the system, the indoor is further provided with a tubular member 90A (such as a ventilation pipe, a fire-fighting pipe and other pipelines for passing gas and liquid), a rod member 90B (such as a support rod, a screw rod and other fixing rods required for fixedly installing various devices), which are generally made of steel, and after being irradiated by neutrons, radioactive isotopes with longer half-life periods, such as cobalt 60, are generated, so as to generate secondary radiation, and in order to reduce radiation damage and radiation pollution to the pipelines and the fixing rods, the tubular member 90A (including the cooling medium and the insulating gas pipeline mentioned above) or the rod member 90B can be made of materials (such as 90% (weight percent) which do not have radioactivity or have low activity after being irradiated by neutrons, or which have short half-life periods, such as C, H, O, N, Si, At least one element selected from Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, Ti, including aluminum alloy, plastic, rubber, or the like) or an annular shield 91 is provided on the outer periphery of the tubular member 90A or the rod-like member 90B. As shown in fig. 18, in one embodiment, the annular shielding device 91 includes an inner housing 911, an outer housing 912, and a shielding material 913 disposed between the inner housing 911 and the outer housing 912; the inner sleeve 911 and the outer sleeve 912 are tubular PVC members, the cross-sectional shapes of the inner sleeve 911 and the outer sleeve 912 can be set according to specific requirements, it can be understood that the inner sleeve 911 and the outer sleeve 912 can also be made of other materials, the products irradiated by neutrons do not have radioactivity, the products irradiated by neutrons have low radioactivity, or the half-life of radioactive isotopes generated after the products irradiated by neutrons is short, for example, the material of the inner sleeve 911 and the outer sleeve 912 is more than 90% (weight percentage) composed of at least one element of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca and Ti, the outer sleeve 912 can also be used as a neutron moderator, and neutrons after moderation can be better absorbed by the shielding material 913; the shielding material 913 is made of a neutron shielding material, such as a boron-containing resin. In one embodiment, liquid boron-containing resin is filled between the inner sleeve 911 and the outer sleeve 912 of PVC, the boron-containing resin is solidified to form an integral annular shielding device 91, the annular shielding device 91 is then cut along the plane of the central axis thereof to two parts, the two parts are wrapped around the cable, the tubular member 90A or the rod-shaped member 90B from two sides, and the two parts are fixedly connected by gluing, bundling, and the like, it is understood that the shielding material 913 may be made of other neutron shielding materials or be disposed between the inner sleeve 911 and the outer sleeve 912 in other forms, and the annular shielding device 91 may be disposed on the outer periphery of the tubular member 90A or the rod-shaped member 90B in other forms, such as penetrating the tubular member 90A or the rod-shaped member 90B into the inner sleeve 911 of the annular shielding device 91 before the tubular member 90A or the rod-shaped member 90B is installed. It can be understood that the annular shielding device 91 may also be disposed on the outer circumference of the cable, so as to further reduce the secondary radiation generated after the cable is irradiated by neutrons.
Although illustrative embodiments of the invention have been described above to facilitate the understanding of the invention by those skilled in the art, it should be understood that the invention is not limited to the scope of the embodiments, and that various changes may be apparent to those skilled in the art without departing from the spirit and scope of the invention as defined and defined in the appended claims.

Claims (10)

1. A neutron capture therapy system comprising a charged particle beam generation unit for generating a charged particle beam, a beam transport unit for transporting the charged particle beam to the neutron beam generation unit, and a neutron beam generation unit for generating a therapeutic neutron beam, wherein the neutron capture therapy system is entirely housed in a concrete-structured building, and a neutron shielding space is formed in the concrete-structured building.
2. The neutron capture therapy system of claim 1, wherein the neutron capture therapy system includes an irradiation chamber and a beam transport chamber, the beam transport chamber at least partially housing the beam transport, the neutron beam generation section at least partially housed within a dividing wall of the irradiation chamber and the beam transport chamber, the neutron shielded space formed within the beam transport chamber or the irradiation chamber.
3. The neutron capture therapy system of claim 1, wherein a neutron shielding plate is disposed on the concrete surface to form the neutron shielding space.
4. The neutron capture therapy system of claim 3, wherein the neutron shield is disposed on the concrete surface by a support assembly, one side of the support assembly being coupled to the concrete and another side of the support assembly being coupled to the neutron shield.
5. The neutron capture therapy system of claim 1, further comprising an auxiliary device around which neutron shield plates are disposed to form the neutron shield space.
6. The neutron capture therapy system of claim 5, wherein the charged particle beam generation section comprises an ion source for producing charged particles and an accelerator for accelerating the charged particles produced by the ion source to obtain a charged particle beam of a desired energy, the neutron capture therapy system further comprising an accelerator chamber at least partially housing the charged particle beam generation section and a beam transport chamber at least partially housing the beam transport section, the auxiliary equipment being at least partially disposed in the accelerator chamber or the beam transport chamber.
7. The neutron capture therapy system of claim 5, wherein an auxiliary equipment room is provided for housing or enclosing the auxiliary equipment, the auxiliary equipment room being at least partially constructed of a support assembly and the neutron shield plate secured to the support assembly.
8. The neutron capture therapy system of claim 7, wherein the ancillary equipment room includes a door and a movement mechanism thereof, the movement mechanism being capable of opening the door for operator access to an interior of the ancillary equipment room.
9. The neutron capture therapy system of claim 8, wherein the movement mechanism includes a guide rail and a slide bar, the door being slidable along the guide rail in a horizontal direction via the slide bar.
10. The neutron capture therapy system of claim 9, wherein the movement mechanism further comprises a lift assembly and a pulley, the lift assembly being capable of lifting the door in a vertical direction to place the pulley at a bottom of the door, the door being capable of sliding in a horizontal direction via the pulley.
CN202220138407.0U 2021-02-09 2022-01-19 Neutron capture therapy system Active CN217448726U (en)

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